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Longxiang Zhu
Longxiang Zhu
Postdoctoral Researcher
在 cqu.edu.cn 的电子邮件经过验证
标题
引用次数
引用次数
年份
Identification of flow regimes in boiling flows in a vertical annulus channel with machine learning techniques
ZJ Ooi, L Zhu, JL Bottini, CS Brooks
International Journal of Heat and Mass Transfer 185, 122439, 2022
212022
Experimental study of boiling flow in a vertical heated annulus with local two-phase measurements and visualization
JL Bottini, L Zhu, ZJ Ooi, T Zhang, CS Brooks
International Journal of Heat and Mass Transfer 155, 119712, 2020
192020
Bubble diameter distribution and intergroup mass transfer coefficient in flows with phase change
L Zhu, ZJ Ooi, JL Bottini, CS Brooks, J Shan
International Journal of Heat and Mass Transfer 163, 120456, 2020
92020
Identification of flow regimes in boiling flow with clustering algorithms: An interpretable machine-learning perspective
L Zhu, ZJ Ooi, T Zhang, CS Brooks, L Pan
Applied Thermal Engineering 228, 120493, 2023
52023
Modeling sensitivity in prediction of interfacial area concentration in boiling flow
L Zhu, ZJ Ooi, CS Brooks, J Shan
Progress in Nuclear Energy 133, 103638, 2021
52021
Two-dimensional quantitative study of boiling flow evolution in vertical inner-heated annulus channel
L Zhu, T Zhang, JL Bottini, CS Brooks
International Journal of Heat and Mass Transfer 183, 122190, 2022
42022
Current Intergroup mass transfer limitations in the multi-group two-fluid model
L Zhu, ZJ Ooi, CS Brooks
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2019
42019
Pore-scale simulation of oxygen transport in a proton exchange membrane electrolysis cell: Effect of the hydrophilia of porous transport layer and catalytic layer
Q Li, Y He, L Zhang, L Pan, H Liu, W Sun, Z Ma, L Zhu, Q Lian, S Tang
Journal of Power Sources 595, 234048, 2024
22024
A study of ammonia-hydrogen-electricity cogeneration coupled to a very high-temperature heat source
B Liu, J Huang, W Chen, W Liu, L Pan, L Zhu, Z Kang
Nuclear Engineering and Design 414, 112585, 2023
22023
Analysis of RELAP5 prediction of countercurrent flow limitation in downcomer at upper plenum test facility
X Li, W Sun, S Ding, T Huang, Z Ma, L Zhang, L Zhu, L Pan
Progress in Nuclear Energy 158, 104608, 2023
22023
Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket
Q Lian, S Tang, L Zhu, L Zhang, W Sun, S Bu, L Pan, W Tian, S Qiu, ...
Nuclear Engineering and Technology 55 (11), 4274-4281, 2023
12023
Evaluation of the models and parameter effects of wall nucleation of liquid sodium
Z Ma, L Zhang, W Sun, L Zhu, S Tang, Q Lian, L Pan
Progress in Nuclear Energy 161, 104728, 2023
12023
Development of a dimensionless flooding correlation based on experimental study on air-water countercurrent flow limitation in a vertical tube
J Wan, W Sun, J Deng, L Zhu, Z Ma, L Zhang, T Huang, L Pan
Progress in Nuclear Energy 153, 104408, 2022
12022
Research on Direct Contact Condensation Model in Core Make-up Tank
Z MA, L ZHANG, L ZHU, W SUN, X ZENG, L PAN
Atomic Energy Science and Technology 56 (8), 1506, 2022
12022
Challenge, State-of-art and Future of Two-phase Flow in Light-water Nuclear Reactor
L PAN, L ZHU, J WAN, W XU, J DENG, M YAN, M HE, L WAN, H ZHANG
Atomic Energy Science and Technology 56 (8), 1483, 2022
12022
Comparison of Intergroup Mass Transfer Coefficient Correlations in Two-Group IATE for Subcooled Boiling Flow
L Zhu, JL Bottini, CS Brooks, L Zhang
Frontiers in Energy Research 10, 890795, 2022
12022
Current capability of interfacial area transport approaches in subcooled boiling
L Zhu, ZJ Ooi, CS Brooks
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2019
12019
Optimizing oxygen transport in proton exchange membrane water electrolysis through tailored porosity configurations of porous transport layers
Q Li, Y He, L Zhang, L Pan, W Sun, Z Ma, L Zhu, Q Lian, S Tang
Applied Energy 370, 123621, 2024
2024
A new numerical method for complex two-phase discharge force based on ARSAC program
D Wu, T Zhang, T Qi, J Deng, L Zhu, J Zhou, C Liu
Progress in Nuclear Energy 173, 105277, 2024
2024
Experimental study of two-phase parameters of subcooled boiling flow in a single-side heated rectangular channel
L Wan, L Liu, L Zhu, Q Ren, Z Ma, L Liu, H Liu, M Yan, L Pan
Progress in Nuclear Energy 173, 105245, 2024
2024
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